EP0234566B1 - Kernreaktornotkühlsystem - Google Patents

Kernreaktornotkühlsystem Download PDF

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Publication number
EP0234566B1
EP0234566B1 EP87102653A EP87102653A EP0234566B1 EP 0234566 B1 EP0234566 B1 EP 0234566B1 EP 87102653 A EP87102653 A EP 87102653A EP 87102653 A EP87102653 A EP 87102653A EP 0234566 B1 EP0234566 B1 EP 0234566B1
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EP
European Patent Office
Prior art keywords
core
flow
water
flow passage
cooling water
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EP87102653A
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English (en)
French (fr)
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EP0234566A3 (en
EP0234566A2 (de
Inventor
Hiroaki Suzuki
Michio Murase
Shigeo Hatamiya
Masanori Naitoh
Kenji Tominaga
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Hitachi Ltd
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Hitachi Ltd
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Publication of EP0234566A3 publication Critical patent/EP0234566A3/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to an emergency nuclear reactor core cooling structure adapted to operate when a coolant is lost due to the breakage of a pipe in a nuclear reactor, and more particularly, to an emergency nuclear reactor core cooling structure having a high operational reliability and being suitable for cooling a reactor core.
  • a conventional pressurized water reactor comprises a pressure vessel, a shroud disposed in the pressure vessel to form a downcomer, a core surrounded by the downcomer and constituted of a lot of fuel assemblies, a lower plenum on the lower side of the core, an upper plenum on the upper side of the core, and cold and hot legs secured to the pressure vessel and communicating with the downcomer and the upper plenum, respectively.
  • cooling water driven by a pump flows from the cold leg in the downward direction in the downcomer, and is guided into the core through the lower plenum.
  • the cooling water is heated with the heat from the fuel in the core, and then guided into a steam generator via the upper plenum and the hot leg.
  • the cooling water returns to the pump and is driven thereby again into the cold leg.
  • a nuclear reactor in the 1,100,000 kW-dass has four such loops.
  • the vapor generated in the core due to the decay heat and the vapor generated in the lower plenum due to the depressurization boiling of the water flow up to an upper core plate partitioning the core and the upper plenum to suppress the falling of the cooling water through bores therein (a CCFL phenomenon). Therefore, a part of the cooling water supplied from the hot leg flows into the loop having a rift, and flows out therefrom. In the meantime, the pressure in the core increases due to the hydrostatic head of the cooling water stored in the upper plenum and a local pressure loss into the core at the upper core plate, and a submergence speed at which the cooling water, injected from the cold leg into the lower plenum through the downcomer flows up in the core is limited.
  • a conventional emergency core cooling structure designed to cool the fuel assembly in a boiling water reactor is provided, on the upper side of the core, with a core spray and a cooling water guide pipe which has a funnel type opening opened on the upper side of the fuel assembly and a plurality of openings in the side wall of the same pipe as shown in Japanese Patent Laid-open JP-A 52 056 298/1977.
  • CCFL phenomenon counter-current flow limiting phenomenon
  • each of the cooling water guide pipes in these prior art emergency core cooling structures serves as a pipe for guiding the vapor, which flows from the openings in the side wall thereof into the same pipe, so as to be discharged to the space on the upper side of the fuel assembly through the same guide pipe.
  • the guide pipe Since the flow rate of the vapor flowing out from the vapor guide pipe is limited, so that the guide pipe does not contribute to the decrease in the quantity of vapor flowing up to the upper tie plate on the upper side of the fuel assembly. Namely, the guide pipe has little effect in introducing the cooling water on the upper side of the fuel assembly into the interior thereof. In order that the cooling water on the upper side of the core or fuel assembly is dropped effectively into the core or the interior of the fuel assembly, it is necessary to consider the mutual effects of the vapor flowing up in the interior of the guide pipe and that of the vapor flowing up in the exterior thereof with respect to a counter-current flow limiting phenomenon.
  • An object of the present invention is to provide an emergency reactor core cooling structure which is capable of effectively cooling a core with cooling water by dropping into the core the cooling water prevented from falling into the core by the steam or vapor flowing up from the core and held on the upper side of the core, thereby to improve the safety of the core when a loss of coolant accident occurs.
  • Another object of the present invention is to provide an emergency reactor core cooling structure which can cool effectively a core with cooling water suppressed to fall into the core by the steam flowing up from the core, by effectively dropping the cooling water without using any driving means such as a pump and a valve, thereby to provide the reactor with a high operational reliability.
  • the structure comprises a core 9, an upper core plate 25 with a flow port 26, and the above-mentioned type of flow passage 22 secured to the upper core plate and extending therefrom downward into the interior of the core 9.
  • the following explanation is made on the assumption that a cooling water is disposed on the upper core plate 25 and vapor flows up in the core 9.
  • positions a and b indicate the lower and upper portions of the flow passage 22, and a position c the flow port 26.
  • the velocity of flow of the vapor flowing up in the flow passage is controlled at the position a in which the cross-sectional area of the flow passage is reduced.
  • the velocity of flow of the vapor in the position a is substantially equal to that (VgC) of the vapor in the position c owing to the balanced pressures in two plenums separated from each other by the upper core plate 25. Accordingly, at the position b at which the cross-sectional area of the flow passage is larger than that of the flow passage at the position a, the velocity (Vgb) of flow of the vapor decreases in inverse proportion to the cross-sectional area of the flow passage to a level lower than that of the velocity of flow of the vapor at the position c as shown in Fig. 4. Therefore, even when the water cannot fall at the position c due to the vapor flowing up from the underside thereof, it is possible that the water falls from the position b.
  • a curve A shows pressure in the flow passage 22 and a curve B pressure in the core 9.
  • the water flows from the upper side thereinto.
  • the flow rate of the water flowing into the flow passage 22 from the upper side thereof is higher than that of the water flowing out from the lower side thereof, so that the water is accumulated in the flow passage 22, as shown in Fig. 5(b).
  • the fluid resistance increases, and the velocity of flow of the vapor flowing up in the flow passage 22 decreases.
  • the flow passage 22 is filled with the water to attain the pressure distribution shown in Fig. 5(c). If the length of the flow passage 22 is set selectively so that the pressure in the flow passage 22 filled with the water around the position a becomes higher than that in the core 9, the water falls continuously in the flow passage 22. The flow rate of this water is determined depending upon a pressure difference and fluid resistance in the position a.
  • the water can thus fall continuously through the flow passage fixed to the structure provided at the upper side of the core even when the water cannot fall from the flow port 26 formed in this structure, due to the vapor flowing up from the underside of the flow passage. Therefore, the cooling water, which is held on the upper side of the core in case of a nuclear reactor having a conventional emergency core cooling structure, can be utilized effectively for the cooling of the core, and the safety of the core at the time of occurrence of a loss of the coolant can be further improved. Since an amount of the cooling water held on the upper side of the core decreases, the vapor in the core flows out easily. This promotes the reduction of the core pressure, so that the cooling water flows easily into the core.
  • the reactor By providing the reactor with such an arrangement, when the coolant is discharged to the outside of the core by an accident of a loss of coolant in a nuclear reactor, so that the pressure in the core decreases, and then the pressure in the pressure vessel has reached the level of a saturation pressure of the high-temperature water in the water storage tank, the high-temperature water in the tank starts to boil. Owing to the volume expansion due to boiling of the high-temperature water, which is caused by this depressurization boiling thereof, the low-temperature water is injected into the core. In a conventional pressure-accumulated type water injection system, a pressurized gas is used instead of the high-temperature water.
  • the same water-injecting force as in such a conventional water injection system can be obtained by using high-temperature water the volume of which is 1/4-1/5 of the pressurized gas. Accordingly, the operational reliability of the present invention increases without any driving means, such as a valve and a pump.
  • the reactor comprises a pressure vessel 6, a shroud 10 disposed in and secured to the pressure vessel 6 at an upper portion thereof to form a downcomer 3, a core 9 defined by upper and lower core plates 25, 25a and the shroud 10 and having a plurality of (about 200) fuel assemblies 21, and a lower plenum 4 defined on the lower side of the core by the lower core plate 25a, an upper plenum 5 defined on the upper side of the core by the upper core plate 25.
  • a plurality of control rod guide pipes 8 (only one shown in Fig. 7) are disposed and supported by a support plate 25b secured to the shroud 10.
  • the pressure vessel 6 is provided with a cold leg 1 and a hot leg 2.
  • the hot leg 2 communicates with the cold leg 1 through a piping 100 on which a steam generator 103 and a pump are provided. Thus, a liquid flow loop is formed.
  • This type of reactor is provided with four such cooling water circulation lines.
  • the cooling water enters the pressure vessel 6 at the cold leg 1, and it is introduced into the core 9 through the downcomer 3 and the lower plenum 4.
  • the cooling water is heated in the core 9 and then enters the upper plenum 5.
  • the heated cooling water is introduced into the steam generator 103 through the hot leg 2.
  • the heated cooling water is cooled there to generate steam 106 through heat exchange.
  • the cooled cooling water is fed to the cold leg 1 by the pump p through the circulation line 100.
  • cooling water is supplied to the core from a water source 104 through a line 105 with a pump p and a valve v.
  • flow passages 22 are added to the outermost peripheral portion of the core 9 made of the plurality of fuel assemblies 21, and each of the flow passages 22 made of a tubular member such as a tube is fixed to the upper core plate 25 so as to extend vertically therefrom into the core 9. Since the flow passages 22 are provided in a space between the outermost fuel assemblies 21 and the shroud 10 as shown in Fig. 8, the dimensions of the shroud 10 may not be changed.
  • the each flow passage 22 is provided at its lower portion with, for example, an orifice member with a port or orifice 23 for the purpose of minimizing the cross-sectional area of this portion of the flow passage 22.
  • the orifice member 27, which makes the cross-sectional area of the lower portion of the flow passage 22 minimum as compared with those of the remaining portions thereof, can be substituted by a nozzle and a venturi.
  • the length of the flow passage 22 be determined selectively so that the pressure at the lower end of the interior of the flow passage 22 becomes higher than that in the core 9 when the flow passage 22 is filled with water.
  • a minimum length of the flow passage 22 determined on the basis of such conditions becomes 0.08L, wherein L is a distance between the upper core plate 25 and the lower end of the fuel assembly 21. Accordingly, when the length of the flow passage 22 is set to not less than 0.08L, the water in the flow passage 22 falls continuously.
  • the length of the flow passage 22 is preferably 0.08L-0.5L. If the cross-sectional area of the orifice or port 23 is the smallest as compared with those of any other portions of the flow passage 22, the present invention works effectively. As may be understood from Figs.
  • the velocity of flow of vapor at the flow ports 26 in the upper core plate 25 at a point in time at which the velocity of flow of vapor at the upper end 24 of the flow passage 22 becomes Vg o , which represents a velocity of flow of vapor at such a time that the vapor falling up causes the water to be unable to fall becomes Vg o /R, the value of Vg o /R becoming larger as the value of R decreases.
  • the cross-sectional area of the flow port 26 should be set sufficiently larger than a total cross-sectional area of the upper ends 24 of the flow passages 22.
  • the value of R is reduced correspondingly. Consequently, the water can be dropped continuously in the flow passage 22 irrespective of an increase in the flow rate of the vapor.
  • the range of the value of R is preferably between 0.25 and 0.85.
  • the orifice member 27 is preferably tapered at the port 23 as shown in Fig.
  • the orifice may be formed so as to extend not downward but sideways.
  • This embodiment is provided with eight of the flow passages 22, each of which has the orifice the cross-sectional area of which is 71% of that of the upper end 24 of the flow passage 22, the length of the flow passage 22 being 0.38L, the cross-sectional area of the flow passage 22 being 40% of one fuel assembly 21.
  • the cooling water flows down in the core by expansion force generated due to the depressurization boiling of the high-temperature water.
  • the temperature of the cooling water in the lower plenum 4 also reaches a level of saturation, and flashing or depressurization boiling of this cooling water starts.
  • the vapor generated in the lower plenum 4 due to the depressurization-boiling of the cooling water and the vapor generated due to the heat occurring in the core flow up to the flow ports 26 in the upper core plate 25, and the water is prevented from falling into the core through the flow ports 26, so that a water level is formed in the core 9 about five seconds after the occurrence of the breakage of a pipe, and the greater parts of the fuel assemblies 21 are exposed to the vapor (Fig. 12(b)).
  • the velocity of flow of the vapor flowing up through the upper flow port 24 of the flow passage 22 is 71% of that of the vapor flowing up through the flow port 26 since the flow rate of vapor is controlled at the flow passage lower port 23 which has the smallest cross-sectional area.
  • the velocity of flow which is calculated on the basis of the balance between the pressure in the flow passage 22 and that in the core 9, of the water at the lower flow port 23 during this time is 4.9 m/s.
  • the water falling from the lower flow port 23 flows up from the underside of the core 9 as it cools the fuel assemblies.
  • An increase in the speed (re-submergence speed) Vr, which corresponds to the additional provision of the flow passage 22, of the water during this time can be expressed by the following equation on the assumption that the water contains no vapor phase.
  • S i is a total cross-sectional area (m 2 ) of the lower flow port 23 of the flow passage 22; and So a cross-sectional area (m 2 ) of the portion of the core 9 in which the fluids flow.
  • Si/So is 0.012
  • the core re-submergence speed Vr increases by at least 5.9 cm/s. Even when the numbet-o-f the flow passages 22 is increased with the cross-sectional area of each of the flow passages 22 reduced correspondingly, the same effect can also be obtained.
  • the cooling water held on the upper core plate 25 falls speedily into the core 9, so that the vapor generated in the core 9 escapes easily in the upward direction to cause a decrease in the pressure therein. Consequently, due to the balanced pressures in the downcomer 3 and core 9, the water injected from a cold leg 1 in a sound state flows easily from the downcomer 3 into the core 9 through the lower plenum 4.
  • a single-phase cooling mode i.e. a vapor-phase cooling mode can be changed speedily to a two-phase cooling mode, i.e. a gas-liquid-phase cooling mode.
  • a two-phase cooling mode i.e. a gas-liquid-phase cooling mode.
  • the emergency core cooling structure can be operated properly in compliance with any degree of variations in the core output.
  • the core re-submerging speed can be increased by at least 5.9 cm/s by merely adding flow passages to the circumferential portion of the core, and the fuel cladding cooling characteristics can be improved immediately after the occurrence of an accident.
  • FIG. 13 and 14 Another embodiment of the present invention is shown in Figs. 13 and 14.
  • the characteristics of this embodiment reside in that short flow passages 40 are added to the above-mentioned embodiments and the other construction is the same as the previous embodiment.
  • This embodiment is provided with four short flow passages 40, each of which has an orifice member 47 having a flow port 43 the cross-sectional area of which is set to 71% of that of the upper end flow port 44 of the flow passage 40.
  • the length of the flow passage 40 is set to 0.15L, wherein L is a distance between an upper core plate 25 and the lower end of a fuel assembly 21.
  • the cross-sectional area of the flow passage 40 is set 1.6 times as large as that of each fuel assembly 21.
  • the vapor generated due to the depressurization boiling in the lower plenum 4 and the generation of heat in the core 9 flows up through the flow port 26 in the upper core plate 25, and the water which has flowed from the core 9 due to the entrainment (carrying action) of the vapor, the water injected from the hot leg into the upper plenum, or a part of the water held in the upper portion of the core 9 at the time of occurrence of an accident are retained on the upper side of the upper core plate 25.
  • the flow passages 22, 40 are added to the upper core plate 25, and orifice members 27, 47 are provided at the lower portions of the flow passages so that the cross-sectional areas of the lower ports 23, 43 of the flow passages 22, 40 become smaller than those of any other portions thereof. Accordingly, as referred to in the description of the previous embodiment, the water can fall continuously through the flow passages 22, 40 even when the water cannot fall into the flow port 26 of the upper core plate 25.
  • An increase in the core re-submerging speed Vr, which occurs due to the addition of the flow passage 22, is 5.9 cm/s as referred to in the description of a previous embodiment.
  • the velocity of flow of the water at the lower portion 43 which is calculated by taking the balance of pressures in the flow passage 44 and core 9 into consideration, is 2.3 m/s.
  • a value (R) obtained by dividing a total cross-sectional area of the passages at the lower portions 43 of the flow passages 40 by the cross-sectional area of the flow passage portion of the core 9 is 0.024 in this embodiment, and the core re-submerging speed, which occurs due to the addition of the flow passage 40 increases by 5.5 cm/s.
  • the core re-submerging speed increases by 11.4 cm/s while the water level increases up to the lower end 23 of the flow passage 22 after the core has been exposed to the vapor, and by 5.5 cm/s while the water level increases up to the lower end of the flow passage 40 thereafter. If flow passages 22 having a length larger than 0.5L are further added, the speed at which the water level increases up to the lower end of this flow passage can be further increased. According to this embodiment, the core re-submerging speed increases 5.5-11.4 cm/s when only flow passages are added to the circumferential portion of the core. This enables the water level to increase speedily up to the upper portion of the core, and the cooling characteristics of the fuel cladding to improve immediately after the occurrence of an accident.
  • FIG. 15 Further another embodiment of the present invention is shown in Fig. 15. The characteristics of this embodiment reside in that it is made by modifying the embodiment of Fig. 7 by forming a water storage tank 31 in a pressure vessel 6 by an upper core support plate 30, and dividing the water storage tank 31 into a high-temperature water storage space 33 and a low-temperature water storage tank 34 by a partition 32.
  • the high-temperature cooling water (about 290 ° C) flows from a cold leg 1 into the high-temperature water storage space 33 through a leakage bore 35, and into an upper plenum 5 through a leakage bore 36.
  • the temperature of the cooling water is in a low level (about 160 ° C) due to the radiation of heat.
  • a flow passage 22 is added to an upper core plate 25 in the same manner as in the embodiment of Fig. 7, and an orifice 27 is provided in the lower portion of the flow passage.
  • the flow passage 22 is fixed to the upper core plate 25, and the orifice member 27 with a lower port 23 is provided at the lower portion of the flow passage 22 so that the cross-sectional area of the passage becomes the smallest at the lower portion. Therefore, even when the water cannot fall through the flow port 26 in the upper core plate 25, the water falls continuously through the flow passage 22, and the core re-submerging speed increases by at least 5.9 cm/s, as referred to in the description of a previous embodiment.
  • the cooling water does not flow into a rift-carrying loop through by-passing sound loops, so that the emergency core cooling system being actually operated can be effectively utilized.
  • the flow passage 22 displays its effect markedly during a high core-output period which is immediately after the occurrence of exposure of the core 9.
  • the pressure in the pressure vessel 6 decreases to a level which is lower than 65.105Pa (65 atm.), i.e. a saturation pressure at 290 ° C
  • the temperature of the high-temperature cooling water in the high-temperature water storage space 33, the high-temperature cooling water accumulated in the space 33 is depressurization-boiled, so that the volume of this cooling water increases.
  • the low-temperature cooling water held in the low-temperature water storage space 34 is supplied from leakage bores 37 into the upper portions of fuel assemblies 21 through control rod guide pipes 8 to cool the fuel assemblies 21.
  • This core cooling effect produced by utilizing the volume expansion force mentioned above is displayed markedly, especially, between the time at which the whole of the cooling water in the upper plenum 5 finishes falling into the core 9 through the flow passage 22 and the time at which the core 9 is thereafter re-submerged.
  • the cooling water held on the upper side of the upper core plate 25 can be utilized effectively during a high core-output period which is immediately after the occurrence of exposure of the core, and the expansion force generated due to the depressurization-boiling of the high-temperature cooling water is thereafter utilized as a driving power source to supply the low-temperature cooling water directly into the core.
  • This enables the cor-cooling characteristics and reliability of the present invention to be improved.
  • the water storage tank 31, which is provided in the pressure vessel 6 in this embodiment, may be provided on the outer side thereof so as to supply the cooling water into the core 9 through the hot leg 2 or cold leg 1.
  • the high-temperature water can be produced by heating a part of the water in the storage tank by a heater.
  • FIG. 16 and 17 show the interior of a fuel assembly 21.
  • a pressurized water reactor having an electric output in the 1,100,000 kW-class
  • about 200 fuel assemblies are provided, and control rods are not inserted in 75% of these fuel assemblies.
  • the control rod guide pipes of fuel assemblies of 18%, of a total fuel assemblies in which control rods are not inserted are used as flow passages 22.
  • Each flow passage 22 is provided with an upper flow port 24 and a lower port 23 thereof to form a passage by which the space above an upper nozzle 50 and the interior of the corresponding fuel assembly are communicated with each other.
  • a partition 221 is provided in the flow passage 22 and the lower portion has holes 222 for circulating the cooling water.
  • 24 control rod guide pipes are provided per one fuel assembly.
  • the lower flow port 23 is provided at the portion of the flow passage 22 which is 0.4L, wherein L is the length of the flow passage 22, away from the upper end thereof, and the cross-sectional area of this lower flow port 23 is 83% of the flow passage 22.
  • the vapor generated due to the depressurization-boiling of the cooling water and due to the heat generated in the core flows up through the flow port 26 in the upper nozzle 50, and the water which has flowed up from the core by the entrainment of the vapor, the water injected into the hot leg or a part of the water held in the space above the core at the time of occurrence of the accident are retained in the space above the upper nozzle 50. Since the velocity of flow of vapor flowing up through the upper flow port 24 is controlled by the lower flow port 23 having the smallest cross section, this velocity of flow becomes lower than that of the vapor flowing up through the flow port 26.
  • the value obtained by dividing a total cross- sectional area of the lower flow ports 23 of the flow passages 22 by a cross-sectional area of a flow passage portion of the core is 0.01, and the velocity of flow of the water which contributes to the core-re-submerging speed is 4.9 cm/s.
  • the cooling water held above the upper nozzle 50 can be introduced into the central portion, in which the output density is the highest, of the fuel assemblies immediately after the occurrence of an accident, the cooling characteristics of the fuel claddings can be improved.
  • the cooling characteristics of the fuel claddings can also be improved.
  • FIG. 18 A further another embodiment of the present invention is shown in Fig. 18.
  • This embodiment is applied to a boiling water reactor having a dense core in which fuel rods are arranged at short intervals.
  • fuel passages 22 are added in the outermost positions in the core 9 containing a plurality of fuel assemblies 21, the flow passages 22 being fixed to an upper core plate 25.
  • An orifice member 27 with a lower port 23 is provided at the lower portion of each flow passage 22 so that the cross-sectional area of the lower port 23 becomes smaller than those of any other portions of the flow passage 22.
  • the cross-sectional area of the lower port is set to 71% of that of an upper flow port 24 of the flow passage 22, and the length of the flow passage 22 to 0.38L wherein L is the distance between the upper core plate 25 and the lower end of a fuel assembly 21, a total cross-sectional area of the flow passages 22 being set 3.2 times as large as that of a flow passage portion of one fuel assembly 21.
  • the cooling water is heated and boiled with the heat from the plurality of fuel assemblies 21 in the core 9.
  • the vapor generated is subjected to gas-water separation in a separator 65, and the resultant gas is dried in a drier 66 and then sent to a turbine (not shown) through a main vapor pipe 67.
  • the vapor is turned into water in a condenser (not shown).
  • the resultant water is driven by a pump to be returned to a downcomer 3 through a water feed pipe 68.
  • the cooling water returned to the downcomer 3 is driven by an internal pump 70, and flows into the core 9 through a lower plenum 4.
  • the cooling water After the water level has reached the height of the water feed pipe 68, the vapor is discharged but, due to the depres- surizafion boiling of the cooling water, the cooling water continues to be lost, so that the water level continues to lower.
  • the cooling water In order to supply cooling water into the core 9, the cooling water is then scattered in the space above the upper core plate 25 through a core spray pipe 72.
  • the cooling water is not directly supplied to the core 9 taking the thermal stress in the fuel claddings into consideration. If the cooling water is scattered in the space above the upper core plate 25, the water is mixed with vapor, so that the temperature of the cooling water increases to a level near the saturation temperaure thereof. Therefore, the termal stress in the fuel claddings can be reduced to a sufficiently low level.
  • the velocity of flow of the vapor flowing up through the upper flow port 24 of the flow passage 22 is controlled by the lower flow port 23 the cross-sectional area of which is smaller than those of any other portions of the flow passage 22, so that this velocity of flow becomes lower than that of the vapor flowing up through the flow port 26 provided in the upper core plate 25.
  • the velocity of flow of the vapor flowing up through the flow port 26 is higher than a level at which the water becomes unable to flow into the core, the water flows thereinto from the upper flow port 24 of the flow passage 22 against the CCFL characteristics illustrated in Fig. 4.
  • the velocity of flow which is calculated on the basis of the balance between the pressures in the flow passage 22 and that in the core 9, of the water at the lower flow port 23 of the flow passage 22 is 5.3 m/s.
  • the value obtained by dividing a total cross-sectional area of the lower flow ports 23 of the flow passages 22 by a cross-sectional area of a flow passage portion of the core is 0.012, and the portion of the velocity of flow of the water by which the present invention contributes to the core resubmerging speed is at least 6.4 cm/s.
  • the cooling water is introduced into the core after it has been heated to a temperature in the vicinity of the saturation temperature thereof. This enables the thermal stress in the fuel claddings to be reduced to a sufficiently low level, and the core re-submerging speed to increase by at least 6.4 cm/s.
  • FIGs. 19(a) and 19(b) A further another embodiment of the present invention is shown in Figs. 19(a) and 19(b).
  • This embodiment is made by modifying the flow passage 22 shown in Fig. 9 by providing shielding plates 29 formed of a shape memory alloy at the lower portion of the flow passage 22. These shielding plates 29 are closed as shown in Fig. 19(a) during a normal operation (the temperature of the _coolant is about 290 ° C) of the nuclear reactor. Accordingly, the flow rate of the cooling water flowing through the flow passage 22 during a normal operation of the nuclear reactor becomes substantially zero, so that it is unnecessary to increase the capacity of the pump for use in compensating for the cooling water flowing out from the flow passage 22.
  • the shielding plates 29 are opened as shown in Fig. 19(b).
  • the flow rate of the vapor flowing up through the flow passage 22 is restricted by an orifice plate 27 having a flow port 23, of the flow passage 22 even under the conditions which prevent the cooling water in the upper plenum 5 from falling from the flow port 26 in the upper core plate 25 into the core 9.
  • the present invention is capable of preventing an increase in the capacity of the pump used during a normal operation of a nuclear reactor, promoting the advancement of the cooling water into the core when a loss of the coolant occurs, and improving the cooling capacity of the fuel claddings.
  • FIG. 20(a) to 20(c) A further another embodiment of the present invention is shown in Figs. 20(a) to 20(c).
  • This embodiment is made by modifying the embodiment of Fig. 19 by forming an orifice place 27a with a port 23 of a shape memory alloy.
  • shielding plates 29a made of a shape memory alloy are closed as shown in Fig. 20(a).
  • the shielding plates 29a are opened due to a decrease in the temperature of the cooling water as shown in Fig. 20(b).
  • this flow passage 22 is filled with the cooling water, so that the fluid resistance increases, whereby the vapor does not flow from the core 9 into the flow passage 22. Accordingly, when the cooling water in the upper plenum 5 falls into the core 9 through the flow passage 22 with the orifice plate 27a cooled with the cooling water to, for example, not higher than 200 ° C, the orifice plate 27a is opened as shown in Fig. 20(c), to promote the falling of the cooling water.
  • This embodiment is capable of preventing the capacity of a pump used during a normal operation of a nuclear reactor, and promoting the advancement of the cooling water into the core when a loss of coolant occurs.
  • Fig. 21 showing a fuel assembly 21 of a BWR
  • fuel rods 82 are arranged in a square lattice of 8x8, and supported by an upper tie plate 80 with a upper ports 84, a lower tie plate 86 and spacers (not shown).
  • the supported fuel rod bundle is contained in a channel box 87.
  • a lower end of a flow passage 81 made of a tubular member is connected to an upper end of a plug 83 of the fuel rod 82 by a slip joint 85 which is formed in the lower portion of the flow passage 81.
  • An upper end of the flow passage 81 is secured to the upper tie plate 80.
  • small lower flow ports 85a are formed by the outer surface of the plug 83 and the inner toothed surface of the slip joint 85.
  • the total flow passage area of the lower flow ports 85a of the flow passage 81 is made minimal as compared with any other portion of the flow passage 81.
  • Convex portions of the slip joint 85 partially contact with the plug 83 and have roles to prevent the fuel rod 82 from vibrating and to guide the fuel rod 82 in case of absorption of thermal expansion of the fuel rod 82.
  • Concave portions of the slip joint 85 form flow passages 85a when the cooling water on the upper tie plate 80 is caused to flow in the fuel assembly 21.
  • the flow rate of vapor flowing up through the flow passage 81 is controlled by the lower flow ports of the slip joint 85.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heating, Cooling, Or Curing Plastics Or The Like In General (AREA)
  • Details Of Measuring And Other Instruments (AREA)

Claims (10)

1. Wassergekühlter Kernreaktor mit einem Druckbehälter (6), einem in dem Druckbehälter (6) angeordneten und mehrere Brennelemente (21) enthaltenden Kern (9), einem Fluiddurchlaß zur Durchleitung von Kühlwasser durch den Kern und einem Kern-Notkühlsystem, dadurch gekennzeichnet, daß das System mehrere jeweils von einem Oberteil des Kerns in das Innere des Kerns (9) hineinragende und eine Verbindung zwischen dem Kühlwasser auf der Oberseite des Kerns (9) und dessen Inneren bildende Durchlaßkanäle (22) und eine an einem unteren Endteil jedes Durchlaßkanals (22) vorgesehene Fluid-Durchflußbegrenzung (27) zur Reduzierung des Durchlaßquerschnitts des Durchlaßkanals (22) aufweist, so daß die Strömungsgeschwindigkeit des durch den Durchlaßkanal (22) strömenden Fluids am unteren Endteil begrenzt wird und daß das Kühlwasser, welches in einem Kühlwasserverluststörfall von dem im Kern (9) erzeugten und aufwärts strömenden Dampf daran gehindert wird, vom Oberteil in den Kern hinabzuströmen, durch die Durchlaßkanäle (22) gegen den aufwärts strömenden Dampf in den Kern (9) strömt und dabei den Kern (9) kühlt.
2. Kernreaktor nach Anspruch 1, bei dem die Durchlaßkanäle (22) von einer am Oberteil des Kerns (9) vorgesehenen oberen Kernplatte (25) gehalten sind, um senkrecht in das Innere des Kerns hineinzuragen, und bei dem der Fluid-Durchflußbegrenzer eine am unteren Endteil des Durchlaßkanals (22) vorgesehene Mündung (27) ist und eine Öffnung (23) zur Durchleitung eines Fluids hat, so daß der Durchlaßkanal (22) eine minimale Querschnittsfläche am unteren Endteil aufweist.
3. Kernreaktor nach Anspruch 1, bei dem ein Teil der Durchlaßkanäle (22, 40) aus längeren Durchlaßkanälen (22) und der Rest der Durchlaßkanäle aus kürzeren Durchlaßkanälen (40) besteht, wobei alle an einer oberen Kernplatte (25) mit Öffnungen (24, 40) am Oberteil des Kerns (9) montiert sind, so daß die längeren Durchlaßkanäle (22) und die kürzeren Durchlaßkanäle (40) am äußersten Umfangsbereich der Brennelemente (21) angeordnet sind.
4. Kernreaktor nach Anspruch 2, bei dem die Länge des Durchlaßkanals auf 0,08 L bis 0,5 L festgelegt ist, wobei L ein Abstand zwischen einer oberen Kernplatte (25) und dem unteren Ende des Brennelements (21) ist.
5. Kernreaktor nach Anspruch 1, bei dem ein durch Division einer Querschnittsfläche des Fluid-Durchflußbegrenzers (23) des Durchlaßkanals (22) durch die Querschnittsfläche (24) eines oberen Endteils des Durchlaßkanals erhaltenes Verhältnis R auf einen Wert innerhalb des Bereiches von 0,25 bis 0,85 festgelegt ist.
6. Kernreaktor nach Anspruch 1, bei dem der Fluid-Durchflußbegrenzer des Durchlaßkanals (22) durch ein aus einer Legierung mit Formgedächtnis hergestelltes Mündungsbauteil (27) gebildet ist, so daß sich die Querschnittsfläche des Durchlaßkanals (22) am Fluid-Durchflußbegrenzer bei einer hohen Temperatur verringert und bei einer niedrigen Temperatur vergrößert.
7. Kernreaktor nach Anspruch 1, bei dem der Durchlaßkanal (22) an dessen Unterteil eine Blende (29a) aus einer Legierung mit Formgedächtnis zur Abdeckung der Fluiddurchflußbegrenzung enthält, wobei die Blende (29a) die Fluid-Durchflußbegrenzung bei einer niedrigen Temperatur abdeckt und bei einer hohen Temperatur öffnet.
8. Kernreaktor nach Anspruch 1, bei dem das System eine Wasser-Einspritzeinheit mit einem Wasser-Speicherbehälter (31) aufweist, welcher Wasser hoher Temperatur und niedriger Temperatur in einem abgedichteten Zustand enthält, wobei eine Wasser-Einspritzleitung einen Wasser niedriger Temperatur enthaltenden Teil des Wasser-Speicherbehälters (31) und den Kern (9) miteinander verbindet.
9. Kernreaktor nach Anspruch 1, bei dem jedes Brennelement (21) ein rohrförmiges Bauteil für einen Durchlaßkanal aufweist, welches an einer oberen Verbindungsplatte (80) an deren oberen Ende angeordnet ist und ein an dessen unterem Ende gebildetes Schiebeverbindungsteil (85) hat, wobei das Schiebeverbindungsteil (85) mit einem Zapfen (83) an einem Oberteil eines Brennstabes (82) verbunden ist, so daß zwischen dem unteren Ende des rohrförmigen Bauteils (81) und dem Zapfen (83) untere Öffnungen gebildet sind, deren gesamte Querschnittsfläche kleiner ist als die des anderen Teils des rohrförmigen Bauteils.
10. Wassergekühlter Kernreaktor mit einem Druckbehälter (6) einer in den Druckbehälter (6) angeordneten Verkleidung (10) zur Bildung eines Ringraums (3), einem Kern (9), der durch die Verkleidung (10) und obere sowie untere, von der Verkleidung (10) gehaltene Kernplatten (25, 25a) begrenzt ist und darin mehrere Brennelemente (21) enthält, einer von der unteren Kernplatte (25a) im Druckbehälter (6) an der Unterseite des Kerns (9) begrenzten unteren Kammer (4), einer von der oberen Kernplatte (25) im Druckbehälter (6) an der Oberseite des Kerns (9) begrenzten oberen Kammer (5), einem am Druckbehälter zur Verbindung mit dem Ringraum (3) vorgesehenen Kühlzweig (1), einem am Druckbehälter (6) zur Verbindung mit der oberen Kammer (5) vorgesehenen Warmzweig (2) und einem Kern-Notkühlsystem, dadurch gekennzeichnet, daß das System mehrere rohrförmige Bauteile (22, 40) aufweist, die jeweils an einer oberen Kernplatte angeordnet sind, um von dort nach unten in den Kern (9) hineinzuragen und an deren unteren Ende ein Mündungsteil (27, 47) mit einer Öffnung (23, 43) vorgesehen ist, dessen Querschnittsfläche kleiner ist als alle anderen Teile des rohrförmigen Bauteils (22, 40), so daß das Kühlwasser an der oberen Kernplatte (25) in den Kern (9) durch die rohrförmigen Bauteile (22, 40) entgegen dem hochströmenden Dampf hinabströmt und den Kern (9) kühlt, wenn ein Wasserstand in dem Kern abgesenkt wird und Dampf durch Beheizung von den Brennelementen (21) in einem Störfall erzeugt wird.
EP87102653A 1986-02-28 1987-02-25 Kernreaktornotkühlsystem Expired - Lifetime EP0234566B1 (de)

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JP61041788A JPH0684994B2 (ja) 1986-02-28 1986-02-28 非常用炉心冷却装置
JP41788/86 1986-02-28

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EP0234566A2 EP0234566A2 (de) 1987-09-02
EP0234566A3 EP0234566A3 (en) 1988-01-20
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Also Published As

Publication number Publication date
JPS62200292A (ja) 1987-09-03
EP0234566A3 (en) 1988-01-20
US4822557A (en) 1989-04-18
EP0234566A2 (de) 1987-09-02
DE3765133D1 (de) 1990-10-31
JPH0684994B2 (ja) 1994-10-26

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